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IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
IAEA/JAEA INTERNATIONAL WORKSHOPTOKAI-MURA, november 2007
NUCLEAR ENERGY IN THE 21th CENTURY:MAIN TRENDS AND POSSIBLE SCENARIOS IN FRANCE
Bernard BOULLISProgram Director for fuel cycle technologies and waste management
CEA, Nuclear Energy Division
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NUCLEAR POWER PLANTS in FRANCE• 34 900 MWe units• 20 1300 MWe units• 4 1500 MWe units
GRAVELINES
CHOOZ
CATTENOMNOGENT / SEINE
ST-LAURENT
CHINONCIVAUX
LE BLAYAIS
GOLFECH
CRUAS
TRICASTIN
ST-ALBAN
BUGEY
DAMPIERRE
PENLYPALUEL
FLAMANVILLE
BELLEVILLE
FESSENHEIM
58 units63 GWe installed415 net TWh in 2004
Connection to the grid :– Unit 1 (Fessenheim 1) : 1977– Unit 58 (Civaux 2) : 1999
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
FRENCH ELECTRICITY
0
100
200
300
400
500 TWh
1950 1960 1970 1980 1990 2000
541
Hydro
Nuclear
Fossil
64
421
57
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
CO2 RELEASE AND ELECTRICITY GENERATION
Source AIE 2006
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NUCLEAR ENERGY IN FRANCE
• 58 LWRs (and PHENIX !)• >75 % ELECTRICITY SUPPLY
• A « CLOSED » FUEL CYCLE :
– UOX SPENT FUEL REPROCESSED
– U RECYCLED ( 2 REACTORS)
– Pu RECYCLED (20 REACTORS) (from 1987)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
SPENT FUEL REPROCESSING AND RECYCLING
LA HAGUE
MARCOULE
MELOX PLANT100t/Y (220 fuel assemblies)
>1200t manufactured
UP2-UP3 PLANTSup to 1600t/y (F+others)>20 000 t processed
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
> 10.000 GLASS CANISTERS
Hulls ( compacted)
180 liters15% FPs oxides
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Reactors --> ≈ 420 TWhe/yr(from MOX fuel : 30 to 40 TWhe/yr)
Spent Fuel cooling pools
Reprocessing≈ 850 HMt/yr
• HL Waste :--> glass canisters (120m3)--> hulls canisters (180m3)
• final disposal whenavailable...
MOX Fuel100 HMt/yr
≈ 220 fuel assemblies/yr
Recovered Uranium
UOX fuel fabrication≈ 1000 HMt/year
Uranium≈ 8000 t/year
Enrichment≈ 5,5 MSWU/year
Plutonium40 HMt/yr
enrichment
TODAY FRENCH CLOSED FUEL CYCLETODAY FRENCH CLOSED FUEL CYCLE
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
The closed fuel cycle strategy, along with reprocessingand MOX recycling, enables today, with existing facilities :
• Reduction / stabilization of spent fuel quantity : 7 UO2 spent fuel → 1 MOX spent fuel
•Vitrification of high level nuclear waste :•a safe and long-lasting confinement, an international standart• a reduced volume: around 1200 m3 today, and up to 5000 m3 in 2030
• Recycling of plutonium and recovered uranium30% Pu is consumed, produces up to 40 TWh/yr (up to 10% production)
• Preservation of long term energy resourcesconcentration of Pu in MOX spent fuel under a reduced volume, leaves open the possibility to reuse Pu in the future
A CONTRIBUTION TO SUSTAINABILITYA CONTRIBUTION TO SUSTAINABILITY
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
SPENT FUEL INTERIM STORAGESPENT FUEL INTERIM STORAGE
Spent Fuel inventory HMt
0
10000
20000
30000
40000
1997
2000
2003
2006
2009
2012
2015
2018
2021
2024
2027
2030
HMt
total UO2 + MOX SF MOX SF total SF if end reprocessing total SF pool storage capacity NPPs + LH
410TWhe/year :
hyp: end of reprocessing monorecycling in
2004
Avoided by recycling
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
A FIRST TRACK FOR THE FUTURE:
• RECYCLE PLUTONIUM INTO GEN3 LWRs !
• Necessity to avoid spent fuel accumulationwhen worldwide « nuclear renaissance » is there!
• Today’s technology as an efficient basis,possibly improved by uranium-plutonium co-management(COEX process, no « pure plutonium stream »)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Reactors --> ≈ 420 TWhe/yr(from MOX fuel : 30 to 40 TWhe/yr)
Spent Fuel cooling pools
Reprocessing≈ 850 HMt/yr
• HL Waste :--> glass canisters (120m3)--> hulls canisters (180m3)
• final disposal whenavailable...
MOX FuelMelox ≈ 100 HMt/yr≈ 220 fuel assemblies/yr
Recovered Uranium
UOX fuel fabrication≈ 1000 HMt/year
Uranium≈ 8000 t/year
Enrichment≈ 5,5 MSWU/year
Plutonium40 HMt/yr
enrichment
TODAY FRENCH CLOSED FUEL CYCLETODAY FRENCH CLOSED FUEL CYCLE
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
HALL WASTE : THE 1991 FRENCH ACT
• 3 RESEARCH THEMATICS :
– partitionning & transmutation of LLRNs ;
– deep repository ;
– confinment & interim storage.
• 2006 : a public debate, and a new bill
30, december, 1991
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
THE 2006 FRENCH ACT
ENOUNCES PRINCIPLES :
– RECYCLE (reprocess)to decrease waste amount & toxicity
– RETRIEVABLE GEOLOGICAL REPOSITORYthe reference option for ultimate wastemanagement.
28, june, 2006
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
THE 2006 FRENCH ACT …
PRECISES A « ROADMAP » :
– 2012 : assess the industrial potentialitiesof diverse P&T options(prototype by 2020)
– 2015 : repository defined(operation by 2025)
28, june, 2006
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
PRESENTATION OF THE 2006 FRENCH ACT
“With this text, the Government doesn’t propose to you a definitive
solution to the question of radwastemanagement; he proposes to take time enough to implement (step by
step) the solution ….”
François LOOS, Minister for IndustryFrench Parliament, 6 april 2006
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NUCLEAR ENERGY IN FRANCE: TRENDS FOR THE FUTURE
A « CLOSED FUEL CYCLE » !
– WITH CURRENT GEN II LWRs
– THEN WITH GEN III EPRs
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
GENERATION III ADVANCED REACTORS
- A new generation of reactorstaking advantage of the large experience acquired in the operation of Gen II plants (LWRs mainly)
- a main objective: new improvements in safetywhile improving economic competitiveness
- Mitigation of severe accident consequence, major goal
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
FLAMANVILLE 3 : EPR in FRANCE
(site permit april 2007, operation by 2012
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Gen III REACTORS FEATURESGenGen III III reactorsreactors suchsuch as EPR as EPR maymay help help to to reducereduce the plutonium the plutonium inventoryinventory
Plutonium annual balance(Kg Pu/year)
REP 900 UO2 : + 200
REP 900 MOX : 0
EPR 100% MOX : - 670
MOXUOXControl rods
EPRREP 900
An enhanced capacityto burn PlutoniumCapacity to load up to 100% MOX Core
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
(1) COSTS
(2) SAFETY
MAIN CRITERIA FOR FUTURE NUCLEAR SYSTEMS
(3) « SUSTAINABILITY » :. rational use of natural resources. waste minimization. resistance vs. proliferation risks
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NUCLEAR ENERGY IN FRANCE: TRENDS FOR THE FUTURE
A « CLOSED FUEL CYCLE » !
– WITH CURRENT GEN II LWRs
– THEN WITH GEN III EPRs (1st Unit, 2012)
– THEN WITH GEN IV FAST REACTORS:• Uranium & plutonium (fuel resource extended)• Americium, Neptunium, Curium ?
(radiotoxicity decreased, …)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
FAST REACTORS PROJECTS
60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03595857
RAPSODIE
PHENIX
SUPERPHENIX
EFR
Studies & design Construction DecommissioningOperation
1st criticality
1st connection to the grid Final shutdown
01/67
02/98
08/73 12/73
09/85 01/86
40 MWth
250 MWe
1200 MWe
1500 MWe
10/83
SPX 2
60’s 70’s 80’s 90’s
till 08
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
FROM GENERATION III TO GENERATION IVLWRs: many advantages,
but can’t satisfy alone sustainability.
Sustainability requires fast neutron systemsto efficiently burn plutonium, and fully use uraniumto reduce efficiently long-term radiotoxicity.
new concepts at industrial maturity :two or three decades(Gen III deployement & operation)
Plutonium stored in spent LWR- MOX fuelscould allow around 2040 the progressive start-up of several fast reactors.
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
FRENCH PRESIDENT, 6 january, 2006
« …many countries think to the next generation of nuclear reactors, for 2030-2040, which will produceless waste and will use in a better way fissile materials . I decided to launch now the design, by the CEA teams, of a prototype of such a reactor, whichwill be commissionned by 2020.We will cooperate, obviously, with industrial and international partners who would propose to joinus in this project… »
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NUCLEAR ENERGY IN FRANCE: TRENDS FOR THE FUTURE
A « CLOSED FUEL CYCLE » !
– WITH CURRENT GEN II LWRs(today 22 years old in average)
– THEN WITH GEN III EPRs(1st Unit, 2012 )
– THEN WITH GEN IV FAST REACTORS(transition from 2040?)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
AND HYDROGEN GENERATION ?AND HYDROGEN GENERATION ?
Storage
Leak detectionon production
columns
Separationhill
Underground reactor building
Distance
Regulations
(artist view)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Generation 3+
Generation 4Existing fleet40-year plant life
Plant life extension beyond 40 years
0
10000
20000
30000
40000
50000
60000
70000
1975
1980
1985
1990
1995
2000
2005
2010
2015
2020
2025
2030
2035
2040
2045
2050
2055
2060
Average plant life : 48 years
Scenario for the renewal of French NPPs
Source : EDF
Inst
alle
d ca
paci
ty (M
We)
60 000
Major role of LWRs over the 21st century
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Generation 3+
Generation 4Existing fleet40-year plant life
Plant life extension beyond 40 years
0
10000
20000
30000
40000
50000
60000
70000
1975
1980
1985
1990
1995
2000
2005
2010
2015
2020
2025
2030
2035
2040
2045
2050
2055
2060
Average plant life : 48 years
Scenario for the renewal of French NPPs
Source : EDF
Inst
alle
d ca
paci
ty (M
We)
60 000
Major role of LWRs over the 21st century
EPR, 1st of a kind
Fast reactor Prototype
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
GUIDELINES FOR THE PROTOTYPE…- SFR, the référence option
- near 600 MWe, loops or pool, ..?.
- increased safety ,competitivity, iso-generation,easier in-service inspection …
-GFR, the main alternative-access to high temperature applications …
-International cooperation, an experimental reactor possibly in Europe (50 MWth)?
-A « challenging » fuel !
-ADS , in the frame of international programs
-
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
Generation 3+
Generation 4Existing fleet40-year plant life
Plant life extension beyond 40 years
0
10000
20000
30000
40000
50000
60000
70000
1975
1980
1985
1990
1995
2000
2005
2010
2015
2020
2025
2030
2035
2040
2045
2050
2055
2060
Average plant life : 48 years
Scenario for the renewal of French NPPs
Source : EDF
Inst
alle
d ca
paci
ty (M
We)
60 000
Major role of LWRs over the 21st century
LH plants, 40 years operation
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
A POSSIBLE SCENARIO IN FRANCE…
Source: EDF - ENC 2002
OperatingFleet
1975 2000 2025 2050 2075
FR
EPR
U (recycled)
Pu (once recycled, MOX fuel)
M.A. + F.P. ---> GlassF.P. ---> Glass
M.A. ---> glass, or recycle
Recycling in FR
Disposal
Gen IVCycle
Lifetimeextension
REACTORS
FUEL CYCLE
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
WHICH OPTION FOR THE FUTURE ?
R T
U
U PuU & Pu recycled,
COEX
Homogeneousrecycling
R T
U
FP
U Pu AM
R T
U
MAU Pu
FPFP&MA
MA heterogeneousrecycling
R T
U
UU & Pu recycled,
PUREX
Pu
FP&MA R T
U
U Pu
FP
TADS
« double strata »
MA
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
GENERATION IV FUEL CYCLES
• CRITERIA TO FIT : RESOURCE, WASTE ,PROLIFERATION-RESISTANCE
• SEVERAL OPTIONS,WHICH COULD BE SUCCESSIVELY DEPLOYED
• HETEROGENEOUS, HOMOGENEOUS• AMERICIUM, ALL-ACTINIDE…?
• SOLVENT EXTRACTION,INNOVATIVE TECHNOLOGIES ?
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
OPTION FOR HETEROGENEOUS MULTI RECYCLE
• core : UPuO2
• “loaded blankets” : UMAO2(MA =Np/Am/Cm)
PuU
MAs
CORE LB
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
NEW FACILITIES AT LA HAGUE ?
SFR / MOXFUEL
FABRICATION
MINOR ACTINIDES
PILOT( the core of the prototype, tons) (experimental pins,
MONJU demo, kg)
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
en résumé…TODAY FRENCH LWRs FLEET and CLOSED FUEL CYCLE : an efficient, a mature option
GENIII REACTORS provide in the next decades a new optimization step(with optimized technologies for fuel cycle(COEX ?) it could allow a suitable worldwide restart of nuclear energy, avoiding spent fuel accumulation)
To meet sustainability goals, we need the development of Gen IV systems including fast reactors;
Several fuel cycle options including ,minor actinide recycling ,are still matter of R&D,;
By 2012, CEA (and partners) will present a project for a fast reactor prototype and related fuel cycle facilities, to be operated by 2020
IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007
AS A GENERAL RULE …
AT EACH PERIOD OF TIME,TAKE ADVANTAGE OF THE POTENTIALITIES OF THE BEST AVAILABLE TECHNOLOGIES !
GEN III reactors, with appropriate (optimized) technologies for fuel cycle, could allow a suitable worldwide restart of nuclear energy (avoiding spent fuel accumulation), and be used as a “bridge”toward fully sustainable systems